Text

Draft Section C Operating for Salem, Units 1 and 2
	ML041620486
Person / Time
Site:	Salem
Issue date:	06/02/2004
From:	Conicella N; Public Service Enterprise Group
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-272/04-301
	Download: ML041620486 (46)
	v • d • e

Appendix D Form ES-D-I Facility: SALEM I& 2 Scenario No.: NRC #I Op-Test No.: HOTEL Examiners: Operators:

Initial Conditions: 85% Rated Thermal Power, BOL, Equilibrium Conditions Turnover: Unit 2 is at 85% power with the following equipment is out of service: 2A EDG taken 0 0 s 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago for injector maintenance, 21 RHR Pump taken 0 0 s 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago for coupling alignment. Maintenance on both components expected to be completed 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from now. All required surveillances are complete. Weather conditions are normal. Unit 1 is at 100% power. Hope Creek is in a refueling outage. Shift orders are to raise power to 100% at 10% per hour.

~~

Event Event Type* Description N Raise Reactor Power CRSlPO R

RO 2 PRO016B I Pressurizer Pressure Channel 111 Fails Low (TS CRS)

CRSlRO 3 I SJO18OC CRSlPO C 23 SI Accumulator Gas Leak (TS CRS)

C Decreasing Condenser Vacuum ALL

~~

RP0073 M Spurious Turbine Trip, ATWT, Pzr Safety 2PR3 Fails RP0059A&B ALL Open RP0058 C 21 AFW Pump Fails To Auto Start CRSlPO Terminate after SI flow reduction evaluation in LOCA-1 1 (N)ormal, (R)eactivity, (1)nstrumen , (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Revision 9

SIMULATOR SETUP INITIAL CONDITIONS

1. Initialize simulator to IC-xxx, 85% power, BOL, C, xxx ppm

2. Clearance tag 2A EDG

3. Clearance tag 21 RHR Pump

4. Pzr Press and Level Ch Ill selected for control and recorder

1. PZR Safety Valve 2PR3 fails open when Reactor trips (Control Bank D 5 steps)

Description RP0073, Main Turb Trip Failures I Delay No I Ramp No No/No Final Value 4

RP0059A, Failure of Man Rx Trip No No True

)3.)RP0059B,Failure of Man S i l k Trip No No No/No -1 True True I 4. I RP0058, Failure of Auto Rx Trip' I No I No I No/No I True True

5. PROOZOA, Pzr Safety Valve 2PR3 Fails No No No/l True True Open

6. PROOl6B, Pzr Press Ch Ill (PT459) Fails No No 1/No NA 1700 Low

7. SJO18OC, 23 SI Accumulator Gas Leak No No UNO NA 4 18- I CN0086, Loss of Main Condenser Vacuum2 I No I 00:03:00 I 3/No I I 0 50 Page 2 of 10 NUREG-1021, Revision 9

2. RPIOD, 22 MG Set Gen Output Bkr No No 5/No Close Trippe d

3. RP07D, 21 MG Set Motor Bkr No No 6/No Start Stop

4. RP08D, 22 MG Set Motor Bkr No No 7/NO Start Stop 110 OVERRIDE

SUMMARY

No Description Delay Ramp Remote Initial Final I

/Event Value Value I. 6440, OVDl RTB A Trip Switch No No No/No Off Off

2. 6440, OVDI RTB A Trip Switch No No No/No Off Off

3. C310.2E6D Pressure Heater Bus 480V No No No/No Off Off Open Switch

4. C510,2G6D Pressure Heater Bus 480V No No No/No Off Off Open Switch SIMULATOR OPERATOR NOTES I

1 Open Reactor Trip Breakers when the crew has reached Step 14 (reactivity insertion step).

Delete overrides on RBs, then B449, B441, RTB A and B open switch to ON. Also, open all Rod Drive MG Set Breakers:

RT-4, RP007D 21 Motor RT-5, RP008D 22 Motor RT-6, RPOO9D 21 Output RT-7, RPOIOD 22 Output

2. Once the crew has dropped load by approximately 10% on decreasing vacuum, change RT-3 Final Value = 100, Ramp = 0O:OO:OO

3. If requested, turn power off to 2PR6 using Remote Function PR34D, PORV Stop Valve toggled to Tagged.

4. Collect trend data on the following for evaluators:

Reactor Power Turbine Generator Load (MW)

Condenser Vacuum Pressurizer pressure (not Ch 111)

SG NR level (all SGs)

SG WR level (all SGs)

Page 3 of IO NUREG-1021, Revision 9

1 Op-Test No.: I Scenario No.: 1 Event No.: 1 Event

Description:

Unit is at 85% power. Shift orders are to raise power to 100% at 10% per hour.

Time Position Applicant's Actions or Behavior CRS Directs activities associated with power increase

- rod motion

- dilution

-turbine loading RO Adds positive reactivity

- rod motion

- dilution ~~

PO Coordinates with RO to initiate power increase

- operate turbine controls to establish loading rate CRS Makes necessary notifications

- load dispatcher

- operations management Page 4 of 10 NUREG-I021I.Revision 9

Op-Test No.: 1 Scenario No.: I Event No.: 2 Event

Description:

Pressurizer Pressure Channel 111 Fails Low Time Position Applicant's Actions or Behavior RO Responds to alarms.

RO Identifies failure of Pzr Press Ch 111 I Places Pzr Press Master Controller in MANUAL, adjusts demand to current Dressure.

Implements AB.PZR-0001. Directs RO to CRS

- adjust Master Controller output to value obtained from Attachment 1

- select alternate pressure control channel

- return Master Controller to AUTO ~~~~ ~~

RO Selects alternate pressure channel for pressure control RO Places Master Controller in AUTO CRS Directs removal of the failed Pressurizer Pressure Channel from service IAW S2.0P-SO.RPS-O003(Q), Placing Pressurizer Channel In Tripped Condition CRS Refers to TS. Enters TSAS 3.3.1 .IAction . 6 and 3.3.2.1 b. Action19 for failed channel. Enters TSAS 3.4.5b for PORV 2PR1 not operable in AUTO.

CRS/RO Close 2PR6 PORV Stop Valve CRS/RO Direct NE0 to open breaker for power to 2PR6 PORV Stop Valve Page 5 of 10 NUREG-1021, Revision 9

L Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

23 SI Accumulator Gas Leak Position Applicant's Actions or Behavior CRS/RO/PO Recognize indications of problem with decreasing pressure on 23 SI Accum

- Control Console 2CC1 Bezel 1-11 alarm for 23 ACCUM PRESSURE HI/LOW

- indicated Dressure on 2PT-936C and 2PT-937C PO Refers to S2.OP-AR.ZZ-0011 (Q) for 23 ACCUM PRESSURE HVLOW PO NOTIFY the SM/CRS to refer to Technical SDecifications PO Refers to S2.OP-SO.SJ-O002(Q), Accumulator Operation, to restore normal rxessure in 23 Accumulator CRS/PO Raises pressure per procedure:

ENSURE CLOSED 2NT35, N2 HDR ENSURE OPEN one of the following valves:

- 2NT49, UNIT 2 N2 B/U SUP TO ACCUM OR

- I N T Z , UNIT 1 N2 SUPPLY TO UNIT 2 ACCUM OPEN 2NT32, N2 SUPPLY OPEN 23SJ93, N2 SUPPLY When desired pressure is achieved, CLOSE 23SJ93, N2 SUPPLY CLOSE2NT32 Have second operator perform independent verification IAW Attachment 1, Section 8.0 CRS Refer to TS 3.5.1. for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action requirement for inoperable accumulator Page 6 of 10 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Decreasing Condenser Vacuum Position Applicant's Actions or Behavior CRS/RO/PO Recognize indications of decreasing vacuum:

- primary temperature

- steam line pressure

- rise in condenser backpressure

- Alarm OHA G-5,CNDSR VAC LO

- Alarm OHA G-13, CNDSR VAC LO-LO CRS Implements S2.OP-AB.COND-0001 (Q), Loss of Condenser Vacuum.

Directs actions IAW procedure

- initiates Attachment I,Continuous Action Summary

- dispatches operators to look for source of problem per Attachment 2

- directs start of all available condenser vacuum pumps

- directs load reduction at 5 5% per min to attempt to stabilize condenser press

- when required (backpressure > limit in Att 4), initiate rapid load reduction

- implement S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction

- when necessary, orders manual reactor and turbine trips PO Performs actions as directed to address decreasing vacuum:

- dispatches operators to look for source of problem per Attachment 2

- starts all available condenser vacuum pumps

- performs turbine load reduction RO Performs actions as directed to address decreasing vacuum:

- dispatches operators to look for source of problem per Attachment 2

- coordinates with PO to reduce turbine and reactor power

- maintains Tavg on program

- energizes pressurizer heaters

- initiates boration Page 7 of 10 NUREG-1021, Revision 9

Position ADDlicant's Actions or Behavior RO Performs initial actions of EOP-TRIP-1

1. MANUAL Reactor Trip:

- First Handle to Trip.

Second Handle to Trip.

- RTBs to open.

- E6D and G6D to open.

2. Trip not confirmed.

3. MANUAL Turbine Trip.

4. Trip not confirmed.

5. Initiate Main Steam Line Isolation

6. Initiate Control Rod Insertion.

CRS Transitions to EOP-FRSM-I CRITICAL TASK #I Main Steam Line Isolation signal manually actuated within 60 seconds of diagnosis of ATWT conditions.

PO PO reports 21 AFW Pump tripped.

Starts 23 AFW PumD and verifies flow >44E4 Ibm/hr RO Starts 21 and 22 Charging Pumps RO Verifies BIT flow and SJ1.2.4.5. 12. 13 oDen RO Verifies CV40,41,68 &69 closed CRS/PO Dispatches NE0 to open RTBs and Rod Drive MG Set Breakers CRS/PO Dispatches NE0 to close WR70 and151s RO Determines that Primarv Safetv Valve 2PR3 is stuck oDen RO Verifies all PRNls < 5%

Verifies IR startup rate negative CRS Directs chemistry to sample RCS Directs STNRx Eng to perform SDM calculation CRS Returns to EOP-TRIP-1 CRSIROIPO Verify immediate actions of EOP-TRIP-1 RO Closes 2CV139 & 2CV140 with RCS pressure 4 500 psig Page 8 of 10 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event

Description:

Spurious Turbine Trip, A M , Pzr Safety 2PR3 Fails Open CRITICAL TASK #2 With RCS Pressure less than 1350 psig and BIT flow established, secure RCPs prior to exiting EOP-TRIP-I the second time..

RO Stops all RCPs with RCS pressure 4 350 psig CRS/RO/PO ~

Verifies equipment alignment per EOP-TRIP-1 CRS/RO/PO Performs diagnostic activities including:

LOSC SGTR LOCA CRS Transitions to EOP-LOCA-1 Performs faulted SG evaluation Performs ruptured SG evaluation RO/PO Resets SI, Phase A, Phase B, opens 21 and 22 CA330, and resets each I

I SEC and resets 230V Control Centers CRS/RO/PO Performs SI flow reduction evaluation NOTE Terminate scenario on lead evaluators direction after crew has determined that SI flow cannot be reduced.

Page 9 of 10 NUREG-1021. Revision 9

Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

21 AFW Pump Fails To Auto Start

~

Time Position Applicant's Actions or Behavior NOTE: 21 AFW Pump trip should be addressed during the A M (Event #5)

PO PO reDorts 21 AFW PumD trimed. ~ ~~

CRS Directs start of 23 AFW Pump.

PO Starts 23 AFW Pump and verifies flow >44E4Ibm/hr..

I NOTE Terminate scenario on lead evaluator's direction after crew has determined that SI flow cannot be reduced.

Page 10 of 10 NUREG-1021, Revision 9

Appendix D Form ES-D-1 I/ Facility:

Examiners:

SALEM I& 2 Scenario No.: NRC #2 Operators:

Op-Test No.: HOTEL Initial Conditions: 100% Rated Thermal Power, BOL, Equilibrium Conditions Turnover: Unit 2 is at 100% power. Unit 1 and Hope Creek are also at 100% power. Solar magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 0 0 s 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago for motor bearing replacement. AFW pump maintenance is expected to be complete 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months from now. All required surveillances are complete. The crew is directed to maintain Event Malf. No. Event Event No. Type* DescriDtion 1 NIOI93A I PRNIS Channel N41 Fails High (TS CRS)

CRSlRO 2 ------------ -------------.

NE0 Reports Broken Snubber in Aux Building (TS CRS) 3 TU0081H N Main Turbine Governor Valve 24MS29 Fails Closed CRSlPO R

RO 4 VLQ447 C SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To RP0058 CRSlPO Trip, Auto MSLIS Fails to Actuate RP0069 RP0279A RP0279B ___ ~ ___ ~

5 RD0064 C 2 Control Rods Fail To Fully Insert On Reactor Trip CRSlRO 6 EL0273A C Loss of 2A 4 W Vital Bus Offsite sources. 21 EDG fails EL0260 CRSlPO to auto connect with vital bus EL0261 7 AF0183 M Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EL0161 ALL EDGl Terminate when feed flow reestablished to a SG I'

(C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9

SIMULATOR SETUP INITIAL CONDITIONS r

I 1. I Initialize simulator to IC-181, 100% power, BOL, C, 1152 ppm I

2. Clearance tag 22 AFW Pump

3. Ensure 2N41 NOT selected on NIS Recorder 2NR45 EVENT TRIGGERS I 2A 4KV Bus Deenergizes on Reactor Trip (Control Bank D < 5 steps)

I 1.

I MALFUNCTION

SUMMARY

No I Description Remote Initial Final I Event Value Value

1. RP0058, Failure of Auto Rx Trip No/No NA True

2. RP0069. Main Turbine interface Valve NolNo NA True Failure

3. RD0064, Any Rod Fails To Trip (Stuck) No/No NA 4

4. RD0064, Any Rod Fails To Trip (Stuck) No/No NA 44

5. RP0279A, Auto MSLIS Fails to Actuate - No/No NA True 1 1 I 1 1 Trn A 1

I I RP0279B, Auto MSLIS Fails to Actuate - No No No/No NA True Trn B NlOl93A, Power Rng Ch N41 Fails High No No 1/No NA 200 TU0081H, 23MS29 Turb Cntrl Vlv Fails CIS No No 2/No NA True IO. VL0447,22BF19 Fails Closed3 No 00:00:03 3/No NA 0 EL0260,4KV Breaker 24ASD Failure No No No/l NA True

11. EL0261,4KV Breaker 23ASD Failure No No No/l NA True I 12. I EL0273A, 2A DG Bkr Fails To Auto-Close No I NO 1 NO/Nol N A T T r u e I 13. I AFOl83,23 Aux FW Pmp Overspeed Trip' I

~~

No No NA T T r u e

14. EL0161,2A Emer Diesel Generator Trip' No I No 4/NO Page 2 of 11 NUREG-1021, Revision 9

REMOTE FUNCTION

SUMMARY

I I I I I I No Description Delay Ramp Remote Initial Final I Event Value Value

1. AF0025D, 22 AFW Pump Bkr Control No No No/No On Off Power

2. AF0026D, 22 AFW Pump Rack Out No No No/No xxxx 110 OVERRIDE

SUMMARY

I I I I I I No Description Delay Ramp Remote Initial Final

/Event Value Value

1. None SIMULATOR OPERATOR NOTES I

- Trip EDG and 23 AFW Pump shortly after 2A 4 W Bus is re-energized post-trip.

1.

2. After being dispatched to investigate closure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 24MS29 valve actuator.

~

Insert Malf VL0447 (Remote #3) after condensate pump stopped during rapid power reduction or at lead examiner's discretion.

~ ~

4. Collect trend data on the following for evaluators:

Reactor power Turbine Generator load (MW) 21,22,23,24 SG NR level 21,22,23,24 SG WR level Page 3 of 11 NUREG-I 021, Revision 9

Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

PR NIS Channel N41 Fails High Position Applicant's Actions or Behavior CRS/RO Observe indications of channel failure

- numerous alarms on OHA-E

- control rods stepping in

- PR NIS N41 indicating full scale high

- PCS AFD alarms RO Determines PR NIS Channel has failed high. Places ROD BANK SELECTOR SWITCH in MANUAL after obtainina CRS concurrence.

RO Identifies failed channel. Informs CRS.

CRS Refers to S2.OP-SO.RPS-0001 (Q), Nuclear Instrumentation Channel Trip/Restoration to review actions for removing failed channel from service CRS ~~

Notifies I/C Maintenance CRS Reviews TS. Enters LCO 3.3.1.1 Actions 2 and 6 CRS/PO Coordinate to remove channel from service

1. DETECTOR CURRENT COMPARATOR, UPPER SECTION to PRN41

2. Verify CHANNEL DEFEAT lamp lit and OHA E-38 clears

3. DETECTOR CURRENT COMPARATOR, LOWER SECTION to PRN41

4. Verify CHANNEL DEFEAT lamp lit and OHA E-46 clears

5. POWER MISMATCH BYPASS to BYPASS PR N41

6. ROD STOP BYPASS to BYPASS PR N41

7. Verify 2RP1-OVERPOWER ROD STOP MANUAL BYPASS, CH 1 lit

8. Verify OHA E-31 clear

9. COMPARATOR CHANNEL DEFEAT to N41 I O . Verify COMPARATOR DEFEAT lit and OHA E-39 clear

11. At Control Rack No. 26, AXIAL FLUX DIFF MONITOR INPUT TEST SWITCH ItoTEST

12. At Rack No. 2 Protection Ch Set I, A. Ensure OHA A-4 lit

6. Place Bistable Test Switches 2BS-41 I C and 2BS411D in test (up) position

~~ ~

13. Remove both AC control Dower fuses from N41 drawer front CRS/RO/PO Reduce turbine load, if needed to restore Tavg to program CRS/RO If desired. return ROD BANK SELECTOR SWITCH to AUTO Page4of I 1 NUREG-1021, Revision 9

1

~ ~~ ~

Op-Test No.: 1 Scenario No.: 2 Event No.: 2 I Event

Description:

NE0 Reports Broken Snubber in Aux Building Time Position Applicant's Actions or Behavior CRS CRS acknowledges report.

CRS Refers to TS. Enters 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Action Statement for TS LCO 3.7.9.

CRS Initiates action to repair snubber.

CRS May declare affected subsystem inoperable.

Page 5 of 11 NUREG-1021, Revision 9

/1I) Op-Test No.: 1 Scenario No.: 2 Event No.:

Event

Description:

Main Turbine Governor Valve 24MS29 Fails Closed 3

Time Position Applicant's Actions or Behavior CRSlROlPO Observe indications of valve closure:

- Megawatt load will drop rapidly as remaining governor valves open until limited by valve position limiter (VPL)

- Console Alarm TavglTref dev as Tavg rises.

- Steam Dumps will open to attempt to control Tavg

- Pressurizer pressure and level will rise due to change in Tavg, sprays open to control pressure PO Determines that 24MS29 has closed. Informs CRS. Dispatches NE0 to investigate.

CRS Refers to Precautions and Limitations of S2.OP-SO.TRB-0001 (Q),

Turbine Generator Startup Operations. Determines need to reduce power to 5 30% at 5% per minute. Implements S2.OP-AB.LOAD-0001 (a),

Rapid Load Reduction RO Initiates power reduction using rods and boration. Energizes pressurizer heaters. Maintains rods above Rod Insertion Limit.

PO

_ _ _ _ _ ~

Initiates turbine load reduction.

CRS Initiates activities to refill EHC reservior.

CRS Notifies electric system operator and operations management.

PO Stops one condensate pump at -75% power.

NOTE: Insert Malf VL0447 (Remote #3) to fail 22BF19 closed after condensate pump is stopped during rapid power reduction or at lead examiner's discretion.

Page 6 of 11 NUREG-I 021,Revision 9

Time Position Applicant's Actions or Behavior PO ResDonds to feedwater alarms andlor notes channes in BF19 Dosition.

PO Determines 22BF19 is closed, attempts to open in MANUAL, reports that it will not open.

CRS Orders a manual reactor trip.

RO Manually trips reactor PO Attempts to trip turbine. Determines turbine trip not functioning.

CRITICAL TASK # I Initiates MSLl before completion of reading of first 4 steps of EOP-TRIP-I.

RO Determines MSLl required. Manually initiates MSLIS CRS lmdements EOP-TRIP-1 Page7of 1 1 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

Loss of 2A 4KV Vital Bus Offsite sources. 21 EDG fails to auto connect with vital bus.

~~ ~ ~ ~~~~

Time Position Applicant's Actions or Behavior CRS Performs initial actions of EOP-TRIP-1

- Trip Reactor (had to manually trip, 2 rods not fully inserted)

- Is Reactor Trip Confirmed

- Trip Turbine (turbine would not trip, MSlVs closed)

- Is ANY 4 KV Vital Bus energized (2A de-energized)

- Is SI Actuated (SI may be required if delay in closing MSIVs)

RO Reports reactor tripped manually, 2 rods not fully inserted PO Reports turbine not tripped, MSlVs closed PO Reports 2A 4KV Bus de-energized, 21 EDG running unloaded CRS Transitions to EOP-TRIP-2 CRS -

Makes page announcement reactor trip CRS Notifies SM of need to implement Emerclencv Classification Guide PO Controls AFW flow to maintain >22E04 Ib/hr RO Verifies RCPs running, Tavg trending to 547"F, trip breakers open PO Manually closes 21 EDG output breaker, energizes 2A 4KV bus CRS Directs reset of SEC ~

NOTE: Initiate 23 AFW Pump Trip and Loss of 21 EDG Page 8 of I 1 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 2 Event No.: 6 1 Event

Description:

2 Control Rods Fail To Fully Insert On Reactor Trip Time Position Applicant's Actions or Behavior NOTE: Actions may not be taken as SI may actuate.

RO Reports that 2 control rods did not insert on the reactor trip.

RO Starts one BA PP in FAST RO Opens CV175 RO Closes 21CV160 and 22CV160 RO Ensure charging flow is maintained 787 gpm Page 9 of 11 NUREG-1021, Revision 9

Op-Test No.: I Scenario No.: 2 Event No.: 7 Event

Description:

Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDG)

Position Applicant's Actions or Behavior PO PO reDorts loss of flow on 23 AFW PumD.

PO PO reports overspeed trip of 21 EDG.

CRS Directs transition to FRHS-1 when SG level <9% with AFW flow ~22E04 lblhr CRS/RO/PO Verifv RCS pressure > intact SG Dressure CRS Reviews Bleed and Feed initiation criteria with crew RO Stops all reactor coolant DumDs PO Verifies condensate system in operation PO ReDorts SGFP not available due to MSLl RO Initiates SI CRS Directs SI Verification per EOP-APPX-3 RO Resets SI Resets Phase A Isolation Resets Phase B Isolation Opens 21CA330 and 22CA330 Resets each SEC

~~

Resets 230V Control Centers ~~ ~~

RO Stops running RHR and SI pumps. Stops either 21 or 22 Charging Pump CRS Determines SG to be depressurized.

PO Fully opens selected MSIO CRS Directs NE0 to open selected BF40 or BF19 PO Opens selected BF13 PO Opens 21CN48 and 22CN48 PO Closes 21CN32 and 22CN32 PO Reports observed level increase in selected SG and/or CET temperatures lowerinaY CRITICAL TASK #2 Establish condensate flow into at least one SG.

Page 10 of 11 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event

Description:

Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDG)

NOT: Terminate scenario on lead evaluators direction after crew has determined that SI flow cannot be reduced.

Page 11 of 11 NUREG-1021, Revision 9

Amendix D Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC #3 Op-Test No.: HOTEL Examiners: Operators:

Initial Conditions: 3% Rated Thermal Power, MOL Turnover: Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to bonnet leak on Pzr Spray Bypass Valve 2PS4. Mode change is approved. Weather conditions are normal. Unit 1and Hope Creek are at 100% power. Shift orders are to raise power to 50%

hour.

Event Malf. No. Event Event Type* Descrhtion 1 N Raise Reactor Power CRS/PO R

RO 2 PRO017A I Pressurizer Level Channel I (LT459) Fails Low (TS CRS)

~

CRS/RO ~ ____

3 SG0078A C 21 SG Tube Leak (5 gpm) (TS CRS)

ALL 4 BF0105A C 21 Main Feed Pump Trip CRSlPO 5 RCOOl2C C 23 RCP High Vibration CRS/RO 6 SG0078A M SGTR with Loss of Offsite Power EL0134 ALL 7 C Letdown Isolation Valve 2CV7 Fails to Close on Phase A CRSlRO Terminate when depress criteria met (SGTR-I Table F)

I, (R)eactivity, (1)nstrumer (C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9

SIMULATOR SETUP INITIAL CONDITIONS I

1. Initialize simulator to 3% power IC

2. Ensure CH I NOT selected on pressurizer level recorder EVENT TRIGGERS I

1. I None I MALFUNCTION

SUMMARY

No 1.

I Description PROOl7A, Pzr Lvl Ch I (LT459) Failure I

Delay No I

Ramp No I

Remote I Event 1/No I

Initial I

Value 1 Value NA Final I 2.

3.

4.

5.

No SG0078A, 21 SG Tube Leak BF0105A. 21 Main Feed Pump Trip RCOO12C, 23 RCP High Vibration EL0134, Loss of Offsite Power' REMOTE FUNCTION

SUMMARY

I Description I

No No No No Delay I

No No No No Ramp I

2/No 3No 4/N0 5/NO Remote NA NA NA NA Initial 4 True Final

/Event Value Value

1. None UO OVERRIDE

SUMMARY

I I I I I I No Description Delay Ramp Remote Initial Final

/Event Value Value

1. None Page 2 of 11 NUREG-1021, Revision 9

SIMULATOR OPERATOR NOTES I

After Event #5 (23 RCP High Vibration), ramp the severity of the SG tube leak from 5 gpm to 400 gpm over 3 minutes, then initiate the loss of offsite power. .

Collect trend data on the following for evaluators:

21 and 22 SG pressure Pzr pressure 21 and 22 SG NR level Highest CET temperature NI power Page 3 of 11 NUREG-1021, Revision 9

Time Position Applicant's Actions or Behavior CRS Directs activities associated with power increase IAW S2.OP-I0.Z-0003(Q),Hot Standby to Minimum Load:

- rod motion

- dilution CRS Notifies chemistry to suspend 30 min RCS samples and 60 pressurizer samples CRS Initiates Turbine Generator Startup Operations RO Adds positive reactivity

- rod motion

- dilution PO Places MSlOs in AUTO with setpoint 1010 to 1020 psig RO Blocks intermediate range and power range low power trips NOTE: Next event initiated after power increase has begun.

Page 4 of 11 NUREG-1021, Revision 9

L L

Op-Test Event D No.:

0p-Test:No.: I Scenario No.: 3 Event No.:

escription: Pressurizer Level Channel I (LT459) Fails Low

Description:

Position 2

Applicant's Actions or Behavior RO Observes OHA. Identifies that Pzr Lvl Ch I has failed low.

CRSlRO Refers to Alarm Response Procedure for OHA E-36 RO Takes manual control of charging, minimizes charging flow.

RO Selects an operable channel for control, alarm, and recorder.

RO Restores pressurizer heaters, as desired CRS Directs restoration of letdown IAW S2.OP-S0.CVC-0001 (Q), Charging,

~

Letdown and Seal lniection RO Prepares for letdown restoration:

1. Ensures letdown orifice isolations closed (2CV3,4, 5)

2. Ensures 2CC71 in AUTO

3. Opens 2CV7, Ltdn Hx Inlet Vlv

4. Places 2CV18 in MANUAL CLOSE

5. Opens 2C18 until CLOSE (INC PRESS) p/b extinguishes

6. Opens 2CV2, Ltdn Line lsol Vlv

7. Places 2CV2 and 2CV277 (Ltdn Line Is01 Vlvs) in AUTO

8. Places 2CV55 in MANUAL and ADJUSTS chg flow 85-90 gpm

9. Returns 2CA2015, Control Air Supply to CV55 Byp Vlv to NORMAL I O . Adjust 2CV71, as necessary, to maintain 6-12 gpm per pump, not to exceed 40 gpm total RCP seal injection flow RO Restore letdown:

I. Simultaneously

- Opens 75 gpm letdown orifice isolation (2CV4 or 2CV5)

- Adjusts 2CV71 for 6 to 12 gpm per pump

- Adjusts 2CV18 to maintain letdown pressure at 300 psig

2. Ensures Master Lvl Controller in AUTO

3. Ensures pzr level within normal band, places 2CV55 in AUTO

4. Adjusts 2CV18 as necessary and places in AUTO CRS Contacts I&C to place pressurizer channel in tripped condition CRS Enters TS LCO 3.3.1 .IAction 6. May review post accident monitoring TS (only 2 channels required).

Page 5 of I 1 NUREG-1021, Revision 9

~~ ~ ~~

Op-Test No.: I Scenario No.: 3 Event No.: 3 Event

Description:

21 SG Tube Leak (5 gpm)

~ ~ _ _ _

Time Position Applicant's Actions or Behavior PO Reports increasing activity in condenser offgas and 21 SG CRS Refers to AB.RAD-0001(a),Abnormal Radiation CRS Announces increasing activity on 21 SG CRS Notifies SM to refer to Emerclencv Classification Guide CRS Refers to AB.SG-0001 (a),xxxxx PO xxxx.

I I CRS I xxxx I CRS CRS Enters TS LCO 3.4.7.2.c. Action b. for greater than 1 gpm total SG tube leakage and greater than 500 gpd tube leakage in single SG (4 hrs to fix or next 6 to Hot Stby)

I I I NOTE:

Page 6 of 11 NUREG-1021, Revision 9

Time Position Applicant's Actions or Behavior CRS Recognizes trip of the operating main feedwater pump. Enters S2.OP-AB.CN-0001 (Q), Main Feedwater / Condensate System Abnormality..

CRS Verifies reactor power P-10 setpoint. Proceeds to Step 3.14.

I NOTE If CRS chooses to manually trip reactor, initiate the next malfunction.

I CRS Directs RO to reduce power to <5%.

I

5. Sets SG Inlet Vlv demand to 0% (Vlvs 21 through 24AF21)

6. Starts 21 and 22 AFW pumps

7. Controls 21 through 24AF21 to maintain SG levels within 555%of Droaram level (-35% NR levell NOTE Initiate the next malfunction after SG level control established on AFW.

Page 7 of 11 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

23 RCP High Vibration Time Position Applicant's Actions or Behavior RO Observes OHA D-36 RCP VIB HI alarm. Refers to S2.0P-AR.Z-0004(Q), Overhead Annunciators Window D.

- If reactor already tripped, then CRS will direct stopping #23 Page 8 of 11 NUREG-1021, Revision 9

Time Position Amlicant's Actions or Behavior RO/PO Observe indications of increased rate of 21 SG tube leakage. Informs CRS.

CRS Directs manual SI actuation. Makes page announcement. Transitions to EOP-TRIP-1 .

CRS/RO/PO Perform immediate actions of EOP-TRIP-1.

CRS Confirms operability of 4KV vital buses following loss of offsite power, remains in EOP-TRIP-1.

PO Blocks and resets SECs RO Verifies no RCPs running and Tavg 6 4 7 . (Step 21)

PO Throttles AFW to maintain SG NR levels 9-35% fSteD 21 PO Initiates MSL Isolation on loops 21 through 24 (Step 21)

CRITICAL TASK #2 Isolate AFW to the ruptured SG within 10 minutes of initiation of Safety Injection signal.

PO Isolates AFW to 21 SG CRS Determines 21 SG level increasing in an uncontrolled manner.

Transitions to EOP-SGTR-1 (Step 27)

PO Verify valves closed on ruptured SG (Step 4)

MS167 MS Stop MS18 MS Bypass MS7 MS Drain GB4 SG Outlet I PO Stops feeding 21 SG (Step 6)

I CRS I Resets SI, Phase A, Phase B, SECs, and opens cntmt control air isolation valves (21CA330 and 22CS330). Resets 230V Control Centers (Step IO,.

Determines target cooldown CET temperature from Table D.

PO Cooldowns at max rate using intact SG MSIO valves. Stops cooldown at target temperature. ~~

PO Depressurizes RCS using PORV Page 9 of 11 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 3 EventNo.: 6 Event

Description:

SGTR with Loss of Offsite Power II I I It I NOTE: Terminate when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.

Page 10 of 11 NUREG-1021, Revision 9

Time Position ADDlicant's Actions or Behavior PO Determines 2CV7 not closed (Step 10 EOP-TRIP-1).

PO Closes 2CV7 using handswitch.

NOTE: Terminate when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.

Page 11 of 11 NUREG-1021, Revision 9

Amendix D Form ES-D--l Facility: SALEM 1 & 2 Scenario No.: NRC #4 Op-Test No.: HOTEL Examiners: Operators:

Initial Conditions: 100% Rated Thermal Power Turnover: Unit at 100% power. 22 SGFP has a control oil leak. 22 AFW Pump taken 0 0 s two hours ago for motor bearing replacement. All required surveillances are complete.

Weather conditions are normal. Unit 1 and Hope Creek are at 100% power. Shift orders are to reduce power to 60% at 10% per hour to repair SGFP oil leak.

Event Malf. No. Event Type* Event No. Description 1

N: cRslpo Reduce Power to 60% To Repair SGFP Oil Leak R: RO 1 I I I

~~~

2 SG0095D 24 SG Lvl Xmtr (549) Ch II Fails Low (TS-CRS) 1 I CVOO29A 1 CRtRO I Letdown Hx CCW Outlet 2CC71 Fails Closed I

~

Cntmt Area Hi Rad Monitor 2R44B Fails High [TS-CRS]

)I 1 BFOIOSB RD0045 1 C CRSIRO 22 Fd Pump Trip wlUncontrolled Rod Insertion in AUTO 6 MS0088D M 24 MSL Break In Containment, 24 MSIV Fails to Close MS0092H ALL 7 SJ0184A C 21 SI Pump Fails to Auto Start CRSlPO 1 I 9 RP0276A RP0276B RP0277A I C CRSlPO C

1 Phase B Fails to Automatically Actuate Containment Spray Fails to Automatically Actuate RP0277B CRSlPO Page 1 of 14 NUREG-1021. Revision 9

SIMULATOR SETUP INITIAL CONDITIONS I

1. Initialize simulator to IC-181, 100% power, BOL, C, 1152 ppm

2. Clearance tag 22 AFW Pump EVENT TRIGGERS

1. I None I I MALFUNCTION

SUMMARY

No Description Delay Ramp Remote I Event RP0276A, Phase B Fails to Automatically No No No/No Actuate RP0276B, Phase B Fails to Automatically No No No/No Actuate RP0277A, Containment Spray Fails to Automatically Actuate RP0277B, Containment Spray Fails to I No I No I No/No No/No NA NA True True Automatically Actuate SJO184A, 21 SI Pump Fails to Auto Start No/No NA True MS0092H, 24MS167 (MSIV) Fails Open No I T GNO NA True I 1 I N O I I SG0095D, 24 SG Lvl Xmtr (549) Ch II Fails No No UNO NA 0 18- I

~

9.

CV0029A, Letdown Hx CCW Outlet 2CC71 Fails Closed

~~

RM0241A, Cntmt Area Hi Rad Monitor I No No

~

I No No

~

I 2/No 3/NO NA NA True True 2R44B Fails Hi

10. BFOl05B, 22 Stm Gen Feed Pump Trip No No 4/NO NA True

~ ~ ~-

RD0045, Uncontrolled Rod Insertion In No No 4/NO NA True Auto MS0088D, Mn Stm Line (24SG) Rupture No No 5h.b NA True Page 2 of 14 NUREG-1021, Revision 9

REMOTE FUNCTION

SUMMARY

No Description Delay I I

Ramp 1 7;;:; 1 I I Initial Value Final Value I AF0025D, 22 AFW Pump Bkr Control No/No Power 2* I AF0026D, 22 AFW Pump Rack Out r

110 OVERRIDE

SUMMARY

I I I I I I Description Delay Ramp Remote Initial Final

/Event Value Value None SIMULATOR OPERATOR NOTES I

Collect trend data on the following for evaluators:

Reactor power Turbine Generator load (MW) 21 and 24 SG NR level 21 and 24 SG WR level 21 and 24 SG pressure Containment pressure 21 and 24 SG AFW flow VCT outlet temperature Page 3 of 14 NUREG-1021, Revision 9

Time Position Applicant's Actions or Behavior CRS Implements S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction CRS Notifies electric system oDerator and oDerations manaaement.

RO Initiates power reduction using rods and boration. Energizes pressurizer heaters. Maintains rods above Rod Insertion Limit.

PO Initiates turbine load reduction.

PO Stops one condensate pump at -75% power.

Page 4 of 14 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Event

Description:

24 SG Lvl Xmtr (549) Ch II Fails Low

~ ~

Time Position Applicant's Actions or Behavior RO/PO Observes Bezel Alarm for Protection Level Lo-Lo on 24 SG and SG low level lights on 2RP4.

RO/PO Identifies failure low of 24 SG Level Ch II (549). Informs CRS. Refers to S2.OP-AR.ZZ-O014(Q), Control Console 2CC2.

CRS Notifies Maintenance Controls to remove inoperable channel from service IAW S2.0P-SO.RPS-O004(Q), Placing Steam Generator Channel in Tripped Condition.

CRS Refers to TS. Enters TS LCO 3.3.1 .I Item 14 Action 6 CRS Initiates action to reDair channel.

Page 5 of 14 NUREG-1021, Revision 9

~ ~ ~ ~ ~

Position Applicant's Actions or Behavior RO Observes OHA E-41, LTDWN HX OUT TEMP HI. Informs CRS. Refers to S2.OP-AR.ZZ-O005(Q), Overhead Annunciator Window E.

RO Verifies 2CV21 indicates Mixed Bed diversion to VCT at 2CC2.

RO Places 2CC71 in manual and attempts to adjust letdown temperature to

~

= 100°F.

RO Determines that 2CC71 remains closed. Checks status of breaker 2ADC2AX7 (2CC113,2CC215, & 2CC171 LETDOWN DISCHARGE VALVES; located in 2AADC 125VDC Distribution Cabinet).

NOTE: RO will receive report that 2ADC2AX7 did not open. Breaker is closed.

CRS I Directs placing excess letdown in service IAW S2.OP-SO.CVC-O003(Q),

Excess Letdown Flow.

RO Ensures open 2CC215, Excess Letdown HX Inlet.

RO Opens 2CC113, Excess Letdown HX Outlet.

RO Ensures closed 2CV132, Excess Letdown RO Selects 2CV134, Flow to VCT RO Opens 2CV278 and 2CV131, Excess Letdown RO Slowly throttles open 2CV132, Excess Letdown and maintains temperature 4 9 5 F and pressure < I 50 psig while warming system.

RO Adjusts 2CV132 to attain desired ffowrate.

CRS Directs securing of normal letdown IAW S2.OP-S0.CVC-0001 (a),

Charging, Letdown and Seal Injection.

RO I Places 2CA2015, Control Air Supply to CV55 Bypass in BYPASS RO I Adjusts 2CV71 for 6-12 gpm injection per pump.

RO Closes the following valves:

2CV3,2CV4 and 2CV5, Letdown Orifice IsolationValves 2CV2 and 2CV277, Letdown Line IsolationValves 2CV7, Letdown HX Inlet Valve Page 6 of 14 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Event

Description:

Letdown Hx CCW Outlet 2CC71 Fails Closed I I NOTE: Procedural path is listed above. However, CRS should direct the securing of normal letdown prior to establishing excess letdown in order to protect the VCT and RCP seals from excessive temperature. Precaution in S2.OP-SO.RC-O001(Q) Reactor Coolant Pump Operations states the following:

Normal Seal Injection water temperature is SI 30°F. Seal Injection water temperature of up to 190°F is permitted only if RCS temperature is ~400°F.

Page 7 of 14 NUREG-1021, Revision 9

Time Position Applicant's Actions or Behavior PO Identifies Cntmt Area Hi Rad Monitor 2R44B (Stairway to Reactor Sump -

96' Elevation) has failed high. Informs CRS.

CRS Implements S2.OP-AB.RAD-0001 (Q), Abnormal Radiation.

CRS/PO Determine radiation alarm is not valid.

CRS Refers to TS and ODCM.

CRS Enters TS LCO 3.3.6 Item 1.b. Action 26 for inoperable containment area Page 8 of 14 NUREG-1021, Revision 9

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event

Description:

22 Feed Pump Trip wlUncontrolled Rod Insertion in AUTO I I I Time Position I RO/PO Applicant's Actions or Behavior I Observes trip of 22 SG Feed Pump. Inform CRS.

I I I CRS I Page 9 of 14 NUREG-1021, Revision 9

Time Position Applicants Actions or Behavior Page I O of 14 NUREG-I 021, Revision 9

Page IIof 14 NUREG-1021, Revision 9 Op-Test No.: 1 Scenario No.: 4 Event No.: 7

)I Event

Description:

21 SI Pump Fails to Auto Start (1 I

~ ~~~~

Time Position I Applicant's Actions or Behavior Page 12 of 14 NUREG-1021, Revision 9

I Op-Test No.: 1 Scenario No.: 4 Event No.: 8 Time Position Applicant's Actions or Behavior Page 13 of 14 NUREG-I021, Revision 9

Op-Test No.: 1 Scenario No.: 4 Event No.: 9 Event

Description:

Containment Spray Fails to Automatically Actuate 1 Time I Position I Amlicant's Actions or Behavior Page 14 of 14 NUREG-1021, Revision 9

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